From foreword: This report presents the preliminary design of a gamma irradiator intended for use as an experimental hospital sterilizer.

This report is a compilation of available data on ruptures that have occurred since KER start-up. Some of the data presented in this report are inconclusive, but are reported to insure a complete summary of all potential and confirmed ruptures.

G. A. Last reports on metallic uranium irradiation studies: cluster irradiations, tubular element irradiations, MTR-ETR irradiations on NaK capsules, effects of pH on film formation, fuel performance, effect of pressure on swelling, and ETR rupture tests. R. D. Leggett reports on irradiation program, and pore site and distribution in irradiated uranium.

To run a second BPA outage test at the DR-Reactor using the same instrumentation and procedure but increasing the trip-out level fro 800 MW up to a maximum of 1200 MW.

Ex-reactor high temperature, high pressure recirculating water loop defect-tests have been made on SPR size coextruded fuel tubes. The behavior in terms of fuel corrosion loss and fuel shape distortion for ``pin-hole`` type defects has been determined. Effects of annular spacing on the defect-test behavior and the influence on the mechanical and metallurgical conditions of adjacent components has been observed.

This document details activities of the Fuels Preparation Department during the month of September 1960. (FI)

The objective of this test was to irradiate self-supported fuel elements under conditions of severity comparable to those expected for future loadings of this geometry. From this irradiation an attempt was made to determine the resistance to corrosion of cooled cladding, the effect of supports on cladding corrosion and coolant flow patterns, resistance of ``hot-spot`` type of attack, and rupture resistance of projection fuel elements. These results are compared to rib supported control elements in a relative manner. To accomplish this comparison, four shortened columns of 1.47% enriched self-supported fuel were charged into B Reactor on 11-27-59, along with four columns of 1.47% enriched, current geometry fuel under authority of reference 1. As authorized, operating conditions were balanced as closely as possible within equipment and calculational limitations to minimize any ``built-in`` differences between the two materials being compared in order that exposure could be used as the basis for the rupture and corrosion comparisons.

This report documents the research and testing of an automatic alum feed process at the Hanford reservation. This process generates water of varying qualities which is used to cool fuel elements in nuclear reactors.

It is the purpose of this document to provide assistance to the Manufacturing Section personnel in determining their future operating plans. In general, the inter-relationship of such engineering parameters as flow, reactor orificing, rupture performance, etc. has been considered. The effect of these engineering parameters are summed up in the recommendations for ``Operating Plans`` shown graphically in this document. It is to be emphasized that these plans do not reflect operational considerations which may modify the desirability of the indicated level increases nor has allowance been made for major projects, major maintenance outages, or major changes in pile loadings. Many factors, which only operate below or above these ``Operating Plans.`` These plans are based on incremental metal costs and burnout cost estimates obtained from L.W. Lang and are predicated on optimizing plant net return. Should some other basis be selected for examining optimum plant performance some adjustment in the recommended power levels and exposure would be required. It is also to be noted that many of the engineering parameters and basic assumptions which have been factored into these ``plans`` are subject to continual re-evaluation and revision. Thus, in a strict sense, these ``plans`` are outdated even as they are published. …

This report details planning to run a second outage test at the DR-Reactor using the same instrumentation and procedure as an earlier test but increasing the trip-out level from 800 MW up to a maximum of 1200 MW.

The SSA 100 program will compute the buildup and decay of SS materials, (gms Pu, U-235 burnout and uranium burnout) in fuel that has been irradiated in any of the Hanford reactors. The routine input data for the program are the IBM production records supplied by the Production Forecasting and Scheduling Operation. The purpose of this program is to compute and prepare an accurate accountabilty report with a minimum of manual effort. This can either be a report for fuel discharges from the reactors or a report of the entire month end reactor inventory. It is not the purpose of this report to describe in detail the data processing techniques used to provide the accountability reports, this will be left to the discretion of the SS Accountability Operation and the programer. The purpose of this report is to present (1) the technical methods that are fundamental to the program, (2) the necessary instructions that are necessary to make changes or include additional fuel data on the data tape and (3) the necessary instructions such that buildup and decay data can be obtained for fuel elements on a non-routine basis.

Report of the daily cash position for Sugar Land State Bank.

Daily cash report for Imperial Sugar Company including a list of large withdrawals for the months surrounding the date showing the daily expenses and estimated balance for each entry. It also lists scheduled payments for bank loans.

This report describes the operation of the fuels preparation department for the month of October, 1960. Manufacturing, process development, employee relations, financial operations, and plant improvements are discussed.

This document details activities of the Fuels Preparation Department during the month of November 1960. (FI)

The Astron, a thermo-nuclear fusion research machine, requires the injection of high-energy electron at 5 MEV emery level +- 1/2 %, 200 amperes, 60 pulses per second, 0.3 usec pulse width. The accelerator will work by the induction principle with approximately 500 magnetic cores, each 1/2 inch thick lined up on centers. Each core will be pulsed by a single primary turn and the electrons forming the secondary will experience a voltage acceleration equivalent to the primary voltage upon passing by each core. The coupling in this arrangement has been tested and it is very nearly unity.

A flexible foil data processing program is described. Raw data on foil radioactivity are the basic input information required. Output may consists of relative activities, saturated activities, and/or cadmium ratio and flux spectrum data. A statistical analysis of the data is executed with the direct calculation, and errors estimated for the output data.

Abstract: A control system to provide digital printing and to plot an analog trace on an electric operated IBM model 11C Output Writer is described. The Digital mode of operation translates multidigit numbers through a set of commands to print each digit serially, then presents them to the output writer in a time sequence. The Analog mode of operation converts a d.c. input voltage to a digital number and by tab and space bar commands translates the carriage horizontally a distance proportional to this number.

In a recent paper, Bowers and Salpeter described a method for calculating the correlation energy of a classical one-component electron gas. The same problem has been considered by Meeron, Friedman, and Abe, using methods involving the summation of cert infinite classes of diagrams. While the relation between these theories and that of Bowers and Saltpeter is not year clear, it is interesting to note that Abe obtained an equivalent expression by approximating an integral. We have calculated the contribution to the equation of state using Abe's original expression and we found that the equation is valid only for certain values and it gives a correction of the wrong sign. On the other hand, our results are comparable to those which Bowers and Salpeter obtain from higher approximations.

This report is a summary of the aerothermodynamic calculations that have been made during the evaluation of the Tory II-A reactor. A presentation is made of the computational techniques developed, the materials properties utilized, and the calculational results obtained. In addition, relations fundamental to the analysis are discussed

The fabrication, irradiation and evaluation of the first two superheat fuel assemblies is described in detail. Experimental data indicate that, in general, the nuclear superheat fuel elements have performed satisfactorily under the testing conditions used. Certain problem areas which will influence future fuel element designs have been defined.

Monthly report documenting Imperial Sugar operational expenses for the year, broken down by actual sales and production, with estimated operational numbers for the remainder of the year.

In January and February, 1960, Lawrence Radiation Laboratory personnel conducted a series of experiments in Phase II of Project Cowboy in which tourmaline crystal transducers, located very close (3 to 50 feet) to tamped high explosive detonations, detected dynamic elasto-plastic stress waves generated in salt. The detonations occurred 110 feet below the 800-foot working level of the Carey Salt Mine, near Winnfield, Louisiana. These experiments were designed to measure dynamic stress conditions resulting from explosion in the earth media, of which little is known at present, and to provide data for comparative calculations on seismic disturbances from tamped explosions and from explosion in large underground cavities. Eleatic stress waves of 1 kilobar magnitude were observed, with velocities of about 15,000 ft/sec. Inelastic stress waves up to 6 kilobars in magnitude were measured. Velocities for these waves were in the range 9000 to 12,000 ft/sec.

In the course of the cratering studies conducted as part of the Plowshare Program, the dependence of crater dimensions on depth of burst and the scaling laws relating crater dimensions to total energy release have been derived for chemical explosions in the desert alluvium of the Nevada Test Site. The desert alluvium is a lightly cemented sand and gravel, which was chosen for study because the first nuclear cratering explosions were fired in the medium and it was of interest to compare the nuclear and chemical explosion in the same medium. Shoemaker of the U.S. Geological Survey recently completed a detailed analysis of the Arizona Meteorite Crater and, through direct comparison with the nuclear explosion results in Nevada, arrived at an effective depth burst for the meteorite. He also reconstructed the original size and shape of the crater, and determined the limit of brecciation.